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Category:REFERENCE SAFETY ANALYSIS REPORT & AMENDMENTS (RSAR)
MONTHYEARML20042E9171990-04-30030 April 1990
Amend G to C-E SAR Design Certification
ML20011D5171989-12-15015 December 1989
Amend F to C-E Std SAR - Design Certification (CESSAR-DC).
ML20248C3801989-03-30030 March 1989
App 3.11A, Environ Qualification for Structures & Components, to CESSAR Sys 80+ Std Design
ML20247G6661989-03-30030 March 1989
Chapter 1, Introduction & General Plant Description, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20247G6781989-03-30030 March 1989
Chapter 2, Site Envelope Characteristics, to CESSAR Sys 80+ Std Design
ML20247G7141989-03-30030 March 1989
Chapter 3, Design of Structures,Components,Equipment & Sys, to CESSAR Sys 80+ Std Design
ML20247G8511989-03-30030 March 1989
Chapter 4, Reactor, to CESSAR Sys 80+ Std Design
ML20247G8621989-03-30030 March 1989
App 4A Sys 80 Reactor Flow Model Test Program, to CESSAR Sys 80+ Std Design
ML20247G8681989-03-30030 March 1989
App 4B, Hot Loop Flow Testing of Sys 80 Fuel & Control Element Assembly Components, to CESSAR 80+ Std Design
ML20247G9131989-03-30030 March 1989
Chapter 5, RCS & Connected Sys, to CESSAR Sys 80+ Std Design.W/Two Oversize Encls
ML20247G9281989-03-30030 March 1989
App 5A, Overpressure Protection for C-E Sys 80 Pwrs, to CESSAR Sys 80+ Std Design
ML20247G9831989-03-30030 March 1989
App 5B, Structural Evaluation of Steam Line Break for Steam Generator Internals, to CESSAR Sys 80+ Std Design
ML20247G9891989-03-30030 March 1989
App 5C, Structural Evaluation of Feedwater Line Break for Steam Generator Internals, to CESSAR Sys 80+ Std Design
ML20247H0331989-03-30030 March 1989
Chapter 6, Esfs, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20247H2911989-03-30030 March 1989
Chapter 7, Instrumentation & Controls, to CESSAR Sys 80+ Std Design
ML20247H3081989-03-30030 March 1989
Chapter 8, Electric Power, to CESSAR Sys 80+ Std Design
ML20247H3361989-03-30030 March 1989
Chapter 10, Steam & Power Conversion Sys, to CESSAR Sys 80+ Std Design.W/One Oversize Encl
ML20248C3921989-03-30030 March 1989
App 3.11B, Identification & Location of Mechanical & Electrical Safety-Related Sys Components, to CESSAR Sys 80+ Std Design
ML20248B0021989-03-30030 March 1989
App 3A, Discussion of Finite Difference Analysis for Analysis of Pipe Whip, to CESSAR Sys 80+ Std Design
ML20247J0591989-03-30030 March 1989
Chapter 18, Human Factors Engineering, to CESSAR Sys 80+ Std Design
ML20247H4781989-03-30030 March 1989
Chapter 17, QA Program, to CESSAR Sys 80+ Std Design
ML20247H4701989-03-30030 March 1989
Chapter 16, Tech Specs, to CESSAR Sys 80+ Std Design
ML20247H4531989-03-30030 March 1989
App 15C, Analysis Methods for Steam Line Breaks, to CESSAR Sys 80+ Std Design
ML20247H4431989-03-30030 March 1989
App 15B, Methods for Analysis of Loss of Feedwater Inventory Events, to CESSAR Sys 80+ Sys Design
ML20247H4271989-03-30030 March 1989
App 15A, Loss of Primary Coolant Flow Methodology Description, to CESSAR Sys 80+ Std Design
ML20247H4171989-03-30030 March 1989
Chapter 15, Accident Analyses, to CESSAR Sys 80+ Std Design
ML20247H4031989-03-30030 March 1989
Chapter 14, Initial Test Program, to CESSAR Sys 80+ Std Design
ML20247H3971989-03-30030 March 1989
Chapter 13, Conduct of Operators, to CESSAR Sys 80+ Std Design
ML20247H3941989-03-30030 March 1989
Chapter 12, Radiation Protection, to CESSAR Sys 80+ Std Desing
ML20247H3601989-03-30030 March 1989
App 11A, Core Residence Times, to CESSAR Sys 80+ Std Design
ML20247H3531989-03-30030 March 1989
Chapter 11, Radwaste Mgt, to CESSAR Sys 80+ Std Design
ML20247H3161989-03-30030 March 1989
Chapter 9, Auxiliary Sys, to CESSAR Sys 80+ Std Design. W/Four Oversize Encls
ML20150B8181988-06-30030 June 1988
Amend C to CESSAR-DC
ML20151H8191988-04-11011 April 1988
CESSAR-DC Submittal Group B - Revs to Chapters 1,4,5 & 9
ML20236W0531987-09-11011 September 1987
Amend 12 to CESSAR-F
ML20054C1001982-03-31031 March 1982
Amend 7 to CESSAR-F
ML20039D4701981-11-20020 November 1981
Amend 6 to CESSAR-F
ML19350E0871981-06-15015 June 1981
Amend 3 to Chapter 4 of C-E CESSAR-F, Reactor.
ML20003C2771981-02-20020 February 1981
Amend 1 to CESSAR-F
1990-04-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20210R2131997-05-31031 May 1997
Final Safety Evaluation Report Related to the Certification of the System 80+ Design.Docket No. 52-002.(Asea Brown Boveri-Combustion Engineering)
ML20148A8211997-01-31031 January 1997
Abb System 80+ Design Control Document - Volume 1
ML20078Q4311995-02-28028 February 1995
Revs to Sys 80+ Design Control Document
ML20080E2051995-01-0505 January 1995
Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design
ML20076F3301994-10-0707 October 1994
Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design
ML20069N4091994-06-20020 June 1994
System 80+ Certified Design Material
ML20029E1991994-05-0606 May 1994
Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design.
ML20062L8631993-12-31031 December 1993
Certified Design Matl
ML20058E9971993-11-15015 November 1993
Amend T to C-E Std SAR - Design Certification. W/31 Oversize Figures
ML20062J3551993-10-29029 October 1993
C-E Ssar - Design Certification,Amend S. W/15 Oversize Encls
ML20058N1001993-09-23023 September 1993
Rev 2 to Design Alternatives for Sys 80+ Nuclear Power Plant
ML20046B3621993-07-15015 July 1993
Session 3.7;Review of SG Tube Rupture Procedure at Borssele Nuclear Power Station.
ML20045D3421993-06-30030 June 1993
Rev 1 to Design Alternatives for Sys 80+ Nuclear Power Plant.
ML20045C4901993-06-30030 June 1993
Evaluation of Sys 80+ Std Design to Interfacing Sys LOCA Challenges, Special Rept
ML20045C6351993-06-15015 June 1993
Amend P to Sys 80+ Cessar - Design Certification.
ML20044G7061993-05-19019 May 1993
Common Mode Failure Evaluation for Limiting Fault Events.
ML20059F4751993-03-29029 March 1993
Application of Advanced Full Scope Simulators to Severe Accident Precursor Training, Presented at 1993 Simulation Multiconference on 930329-0401 in Washington,Dc
ML20044C0061993-03-17017 March 1993
ABB-C-E Sys 80+ Structural Analysis of Nuclear Island & Nuclear Annex Structures.
ML20044B9411993-02-23023 February 1993
Rev 0 to Human Factors Evaluation & Allocation of Sys 80+ Functions.
ML20012G3351993-02-16016 February 1993
Sys 80+ Advanced LWR PRA-Based Seismic Margin Evaluation.
ML20127M4171993-01-15015 January 1993
Control Complex Info Sys Bases for Nuplex 80+
ML20126F6771992-12-0808 December 1992
Review of CE 80+ FMEA & D&Did Analysis, Technical Ltr Rept
ML20126J0521992-10-30030 October 1992
Amend K to C-E Std SAR - Design Certification
ML20126E6191992-10-30030 October 1992
Amend K to CESSAR - Design Certification. W/50 Oversize Encls
ML20012G3361992-09-30030 September 1992
Draft Basis for Seismic Provisions of UCRL-15910.
ML20114F5611992-09-30030 September 1992
Evaluation of Defense-in-Depth & Diversity in ABB-C-E Nuplex 80+ Advanced Control Complex for Sys 80+ Std Design
ML20104A8501992-09-0202 September 1992
Sys 80+ Design Certification PRA Flood Protection Assessment
ML20104A8551992-09-0202 September 1992
Sys 80+ Design Certification Fire Hazard Risk Assessment
LD-92-095, Draft Sys 80+ Design Certification Piping Analysis Specification1992-08-31031 August 1992
Draft Sys 80+ Design Certification Piping Analysis Specification
ML20101S7281992-07-31031 July 1992
Criteria for Design of Main Control Room & Other Operating Stations for Sys 80+
ML20099D8031992-07-31031 July 1992
Final Sys 80+ Shutdown Risk Evaluation Rept
ML20099D8301992-07-25025 July 1992
Draft Sys 80+ Design Certification Distribution Sys Design Guide
ML20101G5261992-06-15015 June 1992
Draft Sys 80+ Shutdown Risk Evaluation Rept
ML20097A1251992-05-31031 May 1992
Human Factors Engineering Stds,Guidelines & Bases for Nuplex 80+
ML20096F7271992-05-0808 May 1992
Nuplex 80+ Human Factors Design Process Summary
ML20095L5041992-04-30030 April 1992
Draft Sys 80+ Shutdown Risk Evaluation Rept, Part 1
ML20095J2321992-04-30030 April 1992
Rev 0 to Design Alternatives for Sys 80+ Nuclear Power Plant
ML20095A9601992-04-15015 April 1992
Selection of Control Motion for ABB-C-E Sys 80+ Std Design
ML20090K4851992-03-12012 March 1992
QA Program Topical Rept
LD-92-031, Marked-up Copy of QA Program Topical Rept1992-03-12012 March 1992
Marked-up Copy of QA Program Topical Rept
ML20094E9431992-02-11011 February 1992
LOCA Aspects of C-E Advanced LWR - Sys 80+
ML20079C9641991-06-13013 June 1991
Description of Nuclear QA Program
ML20043H2201990-05-18018 May 1990
Seminar on Use of Unusual Event Repts for Improving Nuclear Power Plant Safety.
ML20042E9171990-04-30030 April 1990
Amend G to C-E SAR Design Certification
ML20106D7341990-01-15015 January 1990
Nuplex 80+ Advanced Control Complex Design Bases
ML20096F4761989-12-31031 December 1989
Nuplex 80+ Rev 2 to Verification Analysis Rept
ML20011D5171989-12-15015 December 1989
Amend F to C-E Std SAR - Design Certification (CESSAR-DC).
ML19324B6831989-10-31031 October 1989
QA Program:Description of Nuclear Power Businesses QA Program, Rev 5
NUREG-1044, Sser Supporting Vendor Responses to Confirmatory Item 1, Shutdown Cooling Sys1989-08-0404 August 1989
Sser Supporting Vendor Responses to Confirmatory Item 1, Shutdown Cooling Sys
NUREG-0852, Sser Supporting Vendor Responses to Confirmatory Issue 2, Steam Generator Tube Rupture. Calculated Radiological Consequences of Postulated Steam Generator Tube Rupture Accident Meets 10CFR100.11 Dose Ref Values1989-08-0404 August 1989
Sser Supporting Vendor Responses to Confirmatory Issue 2, Steam Generator Tube Rupture. Calculated Radiological Consequences of Postulated Steam Generator Tube Rupture Accident Meets 10CFR100.11 Dose Ref Values
1997-05-31
[Table view] |
Text
- - - - - - - -
CESSAR !!!nney,.
1 l
APPENDIX 11A CORE RESIDENCE TIMES I
i
)
8904040445 890330 PDR ADOCK 05000470-K PDR
CESSAR 8!nincano,. (Sheet 1 of 1) o EFFECTIVE PAGE LISTING APPENDIX 11A Table of Contents P_ age Amendment i
Text Pace Amendment 11A-1 11A-2 11A-3 O
O Amendment E December 30, 1988
CESSAR !!nifico =
TABLE OF CONTENTS
-APPENDIX 11A Section Subiect Pace No.
1.0 DERIVATION OF CORE RESIDENCE 11A-1 l TIMES j i
[~
CESSAR !! Sinc m.,
O 1.0 DERIVATION OF CORE RESIDENCE TIMES The derivation of the core residence times for circulating crud as shown in Section 11.1.2 is as follows:
A. Circulating Crud:
The number of radioactive atoms (Nf ) in the crud film on in-core surfaces at any time is:
dN g dt *Ed- i 1"f (11A-1)
Solving for N g yields the following:
Ng =
(1 - e ^I #*8) atoms /g (11A-2) i Where: I f
4 is the activation rate for each isotope i (d/g-sec),
A is th decay constant for each isotope f (secs p), and t
res is the desired core residence time (seconds).
The number of radioactive atoms (N c ) released to the reactor coolant at any time is:
[DN=N f [ER] A c ~
("+0+A i) N c atoms /sec Solving for N c yields the following:
Nf (ER) A c "I" + 0 + A 1) t N
o" (a + B + A.) 1 (1 - e ) (11A-3) 2 Where: ER is the erosion rate (g/cm -sec),
A c is the core surface area (cm ),
o is the plateout rate (secs-1),
a llA-1
1 CESSAR E!i#icari:u I
(secs-1),
Oi p is the purification cleanup rate and A
y is the decay constant (secs-1),
Total amount of crud (M ) released to the reactor coolant ;
any time is:
dM dt
=
[ER) A T -( + )M c (11A~4) where M c in ludes both radioactive and nonradioactive material.
Solving for M c yields:
l l M (1 ~ *
- (a + )t) grams (11A-5) c" )
Where: ER is the erosion rate (g/cm -sec),
1 A is the total system area (cm ),
T
~
a is the plateout rate (secs ~ ), and p is the purification cleanup rate (secs ~1).
The activity (Ag) of the crud released to the reactor coolant is:
AN fC A
1=M c , dps per gram of crud in reactor (11A-6) coolant substituting the values of N and M into the above expression and assuming 1.l is shall when compared to a and p, the activity of the crud is as follows:
A c
Ag=If (1 -e ~ i res) (0.06) dpm/mb-crud lu-7) where 0.06 is a constant changing dps/g-crud to dpm/mg-crud.
This activity (A. is also assumed to be the activity of the crud which plated) out on out-of-core surfaces.
Solving equation (11A-7) for t es yields quation (1) (See Section 11.1.2).
11A-2
CESSAR ninneuio B. Denosited Crud The activity (A ) of the deposited crud is 3
A =A gN g = Zy d (1:- e res).0.06 (11A-8)
Solving equation (11A-8) for't res yields. equation (2) . (See Section 11.1.2) 1 i
11A-3